ORNL-TM-7207 - the Molten Salt Energy Technologies Web Site

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and demonstration (RD&D) program; a possible schedule ~ Q major P e ~n- 4 struetion projects; the estimated performance of commercial units; and any special licensing consideratbons. Finally, Sect. 6 presents the gen- eral cbnclusions of the study, along with suggestions that would affect any further work on this concept. G
.. .... . w..w c Y ... . r 5 2. GENEMI, DESCRIPTION OF DMSR The plant concept for a DMSR is a direct outgrowth of the ORNZ reference-design MSBR, and, therefore, it contains many favorable fea- tures of the breeder design. However, to comply with the antfp~~life~a- tion gods, it also contains a number of differences, principally in the reactor CQPQ design and the fuel cycle. matic diagram of the reference-design MSBR. there is only one difference from the DMSR concept: Figure 1 is a simplified sche- At this level of detail, the on-line chemical. processing pliant (shown at the left of the core) would not be required for the DMSR. ,--\ PRIMARY SALT PUMP MODERATOR CHEMICAL PROCESSING PLANT FUEL SALT / NaRF4 ORNL-DWG 68-1185EA r-' SECONDARY I SALT PUMP STEAM GENERATOR Fig. 1. Single-fluid, two-region molten salt breeder reactor.
Page 1: i *w . . I
Page 5 and 6: P iii CONTENTS ....................
Page 7 and 8: CONCEPTUAL DESIGN CHARACTERISTICS O
Page 9: 3 The primary purpose of this study
Page 13 and 14: ii.... :.: ..... .,. \ ..... %& . 3
Page 15 and 16: addition StathQR would be required.
Page 17 and 18: !I \.... . , . ~ .... .. . . / I I
Page 19 and 20: ... .. ...... . . . $i 13 Table 1.
Page 21 and 22: 15 Initial scoping studies showed t
Page 23 and 24: .. . E 6> I S N 0.45 k- 0.50 B --.
Page 25 and 26: :.:..y ,. . . w, E9 The code calcul
Page 27 and 28: h 3. Additional 238Y is added as re
Page 29 and 30: ...z,y .. . c .A, Table 9. Actinide
Page 31 and 32: ';x.w' .... Relative power distribu
Page 33 and 34: ........ . . . :..i 27 a Inner 2.54
Page 35 and 36: 29 Table 16. Effect of neutron spec
Page 37 and 38: ob E 2 a 4 5 6 7 8 9 10 11 12 13 14
Page 39 and 40: .. . . . . . . . . . 'a# 0.1 0.2 0.
Page 41 and 42: 35 (Doppler effect), (2) changing t
Page 43 and 44: where Ci = relative delayed-neutron
Page 45 and 46: .... . . . . , c.y..p c "
Page 47 and 48: .... :...w . . . . . :, %. , dimens
Page 49 and 50: ,. ::.y ~. . .... , 40 0 43 1 2 3 4
Page 51 and 52: .,.,. . . ., , .. . . . . . . . %..
Page 53 and 54: .... ... . ....... . .%.W 3.3.1.1 C
Page 55 and 56: 49 Variation of fuel composition wi
Page 57 and 58: .. .*,p. . . . . . . . Table 25. Ph
Page 59 and 60: ;: c.... x. . w ..i 53 Table 26, St
Page 61 and 62:
would be expected to have an equili
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.... . . . . :i ,.*,&s 57 Corrosion
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. ;;..,..I . . . . . . "LW 0 9 m -
Page 67 and 68:
of the fissioned atom. ea ~arly ass
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63 n e results of a program of solu
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65 Table 27. Sources and rates Sf p
Page 73 and 74:
operation of the PISRE. 67 analyses
Page 75 and 76:
UP3/UF4 ratio would be possible. DM
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$ .p9 3.3.3.1 Preparation of initia
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73 Contamination of fuel by seconda
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*w- through the walls of the primar
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77 4 will apparently be necessary (
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such contamination. For a demonstra
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8% 3.4 Reactor Materials Although s
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: ....., . .’ -. ..WY used in the
Page 91 and 92:
..... i.. ....., . .Yd 85 QRPIL-DWG
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... w . . .y and to salt containing
Page 95 and 96:
With the different ~Bjectives of ns
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t.;$- ... quite different from thos
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93 during noma1 operation. Minor am
Page 101 and 102:
............. . . .. . .=w as SSm,
Page 103 and 104:
. . . :.w . . . . , 4. ALTERNATIVE
Page 105 and 106:
.. . ... . . . . . . .. . . "W 3. T
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.,.. w .." by removing some uranium
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, . . . . . . , -c%w probably still
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and the ~ dvent (or carrier) salt a
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BO 7 TPle fuel makeup requirements
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5. CQPIPIERCIWLPZATION CONSIDERATIO
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11% At the close of MSRE operation,
Page 119 and 120:
12YS 75 22”” 955 30” 1””
Page 121 and 122:
115
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aa 7 some components in common with
Page 125 and 126:
Ae eo un t No * Table 3%. Capital c
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- ,.,.,.,., p .. ..... . G is based
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123 Table 34. Summary of annual non
Page 131 and 132:
...... . . . . ., x.:w* 4 i.. ... _
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E2 7 There are no detailed estimate
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129 particularly if such activities
Page 137 and 138:
. ~.........* . . . . . :*. ... . -
Page 139 and 140:
. .. . . . . . . . ;.:w b 133 the i
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_... ..&/ ; .; with reactor scram m
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137 includlng $900 million for the
Page 145 and 146:
139 The authors want to acknowledge
Page 147 and 148:
. ... . .,.,.,.,.,. . , i.rc- q....
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.:. _.i .. ..... -.=* 45. A. L. Mat
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...... &;.& 3 14 5 74. W, R. Grimes
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p 103. 6. Re Hudson 11, CQNCEPT-5 U
Page 155:
... . . . . . . . , . ,.Y&fl 149 ap
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Account No. -0- Three- digit digit
Page 160 and 161:
.... ..
Page 162:
156 77. He 6. MacPherson, Institute
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